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NUREG-1537, Part 2 Guidelines for P
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AVAILABILlTY NOTICE Availability of
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NUREG-1537, Part 2, has been reprod
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Page 4 REACTOR DESCRIPTION ........
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- | CON1, Page 12.6 Records .......
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ABBOEVW7!NS IAEA International Atom
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INTRODUCTION Background Ts document
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NTRODUCMON accidents, since the maj
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INTRODUCnION reviewers dealing with
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IRODUCriON accident consequences. T
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1 THE FACILITY Chapter 1 of the saf
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* safety criteria proposed by the a
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THE FACILITY SAR. The technical spe
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Evaluaton Findings NRC does not wri
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THE FACILTIY Applicants are expecte
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* assumed inventory of fission prod
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ThE ForAaXy agreement with the Depa
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Appendix 1.1 Introduction from NURE
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Appendix 1.2 DOE Letter to NRC Conc
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2 SIT CHARACTERISCS This chapter pr
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SnE CHARAcrmusncs * The demographic
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SIE CHARAcXERIcs * historical seaso
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SrYI CHARAcrIsnTc other water-induc
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SrnE CHARAcYmusna * The geologic fe
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3 DESIGN OF STRUCTURES, SYSTEMS, AN
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DESIGN OF STRUCTURES, SYSTEM, AND C
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DESIGN OF SRUCrURES Sysms. AND COMP
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Evasion Findings - DESIGN OF STRucn
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DESIGN OF STRnUtURES, SYSTEMS, AND
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CHAPTER 4 reactor core. Subsequent
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CHAPTER 4 * The discussion of the f
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CHAPTER 4 * The control rod design
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CHAPTER4 * materials * compatibilit
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CHAPrER4 when starting the reactor
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CHAPT 4 * The applicant has justifi
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CHAFtE4 characteristics of the reac
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CHAPTER4 Review Procedures The revi
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CHAPrER4 calculational models and a
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CHAPTER 4 Anticipated rearrangement
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CHAPTER 4 4.5.2 Reactor Core Physic
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CHAPTER 4 included them in the tech
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CHAPTER. 4 Evaluation Findings This
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CHAPTER 4 For a pulsing reactor, li
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CHAPTER5 This chapter gives the rev
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CHAPTER S The descriptions and disc
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CHAPTRS acceptable radiological dos
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CHAPTER 5 dissipation is accomplish
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CHAPTER 5 5.4 Primary Coolant Clean
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CHAPTERS achieved. The design ensur
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CHAPTERS Ewauation Findings This se
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CHAPTR5 Evaluation Findings This se
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CHAPTER5 analyzed. The reviewer sho
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- Page 135 and 136: -.... - . INSTRUMENTATION AND CONTR
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- Page 149 and 150: . AuxiLARY SYSTEMS * Methods for in
- Page 151 and 152: Evaluation Findings AuxnARY SYSTEMS
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- Page 159 and 160: AuxILIARY SYSTEM * analyses of the
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- Page 203 and 204: CHAPTER 12 day-to-day operation of
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CHAPTER 12 staff has determined tha
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CHAPE 12 to correct and prevent rec
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CHArER 12 12.6 Records Areas of Rev
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CHAPrER 12 * requalification docume
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CHATRi 12 operator skills and knowl
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CHAPTER 12 applicant's safety analy
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Appendix 12.1 Environmental Conside
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APPENDvc 12.1 Chemical and sanitary
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APPENDix 12.1 Conclusion The staff
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CHAPTER 13 The information in this
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CHAPSER 13 * The single malfunction
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CHITER 13 (c) (For high-powered rea
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CHAPTER 13 or * protracted malfunct
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CHAPTER 13 * With natural-convectio
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CHAPTER 13 (If the MHA is not afuel
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CHAPTDl 13 Bibliography Non-Power R
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CHAPShR 13 U.S. Nuclear Regulatory
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14 TECHNCAL SPECIFICATIONS This cha
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TEcHnICAL SpEcmcAnoms * The staff h
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CHAPTER 15 * Areas of review should
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CHAnM R1S * The applicant should es
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CHAP~i~tIS Environmental Review Pro
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CHAPD 16 system; engineered safety
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CHAF1a 16 Medical therapy at non-po
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CHAPS 16 treatment. The door or ent
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CHAEW 16 * Requirements for reporti
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17 DECOMMISSIONING AN) POSSESSION-O
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- DEcOM iSNNG AND PossEssION-ONLY A
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DEcOmm oNG ANDPossEsoN-ONLYAmm .ES
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Review Procedires DEamRsoNEA PosHmo
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DEcOmmXsoNU4G AD PossEssioN-ONLY AM
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DEcoMMiSsIoNING AND PossEssioN-ONLY
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NRC Review of Decommissioning Plan
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2.2.2 Current Radiological Status o
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DEMMM=ONMPJANS 2.4 Decommissioning
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DECCMMISSIONI0PLANS The DP should s
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DEco wIssioNDJGPLA controls to comp
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- - ~DECOM SSOKMGPLANS facility. Su
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8 ENVIRONMENTAL REPORT ..DECOMOM=ON
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18 HIGH1LY ENRICHED TO LOW-ENRICHED
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NIowLy ENmI ToLow-EmIAEDURAwrum CoN
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Standard Review Plan and Acceptance
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HEU To LEU CoNvEaswoN since the las
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HEU To LEU CONVERSION should also d
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HEU TO LEU CoNVERSION this section,
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4.2.1 Fuel Elements HEU TO LEU CONV
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Evaluation Findings (Sections 4.2.1
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Acceptance Criteria _HEU TOLEU CoNv
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- HEU TO LEU CONVERSON Calculations
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HEU TO LEU CONVERSION should be dis
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HEU TO LEU CoNvERSoN *Acceptable ch
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BEU To LEU CoNvEasioN Generally, co
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Evluation Findings HEU TOLEU CONVER
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... HEU TO LEU CONVERSION * The coo
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Accepktace Criteria HEU To LEU CONV
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9.4 Fuel Element Handling and Stora
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10 EXPERIMENTAL FACILITIES AND UTIL
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11.1 Radiation Protection Program A
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*HEU TOLEU CONVERSION The areas of
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BEU TO LEU CONVERSION specification
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- - - - HEU To LEU CoNvmESioN relia
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HEUrTo LEU Cowv~ptstoN design ofthe
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BIEU To I.EU Col~vERSoN MHA, the ba
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HEU To LEU CoNvRiow acceptable assu
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Review Procedures -- HEU TOLEU CONV
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13.3.1 Loss-of-Coolant Accident Are
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HEU To LEU CONVERSION methods and a
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Evaluation Findings BEU To LEU Comv
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BEU TO LEU COPvERSION characteristi
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HEU TOLEU CONVON American National
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HEU TO LEU CONVERSION U.S. Nuclear